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Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
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Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
Partner: UNT Libraries Government Documents Department
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Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Quarterly Progress Report: October 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.
Date: February 21, 1958
Creator: MacPherson, H. G.
Partner: UNT Libraries Government Documents Department
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Standard Practices for Design of MTR and ETR Safety Circuits

Description: Report containing notes for designing safety circuits for the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR).
Date: September 15, 1957
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department
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Supplement to Standard Practices for Design of MTR and ETR Safety Circuits

Description: Report that offers updated information from the Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) "experiment safety circuit manual by providing ETR power reduction curves and other information on ETR not yet available at the time the manual was issued, September 15, 1957" (p. 1).
Date: November 21, 1958
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department
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Distribution of Uranium at Low Acid : Low Uranium Concentrations into 4-1/2 Percent TBP-AMSCO

Description: Report wherein acid free uranyl nitrate hexahydrate was distributed into 4-1/2 percent TBP-Amsco 125-90W and combined with various concentrations of acid in order to study the distribution of uranium and hydrolysis effects.
Date: August 23, 1956
Creator: Andelin, Robert L.; Anderson, Edward L. & McVey, W. H.
Partner: UNT Libraries Government Documents Department
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MTR Technical Branch Quarterly Report, Third Quarter

Description: Quarterly report for the technical branch of the Materials Testing Reactor of Idaho. Includes current developments and experiments.
Date: November 1, 1956
Creator: Conner, W. P.
Partner: UNT Libraries Government Documents Department
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Design Bases for ICPP Waste Calcination Facility

Description: Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
Partner: UNT Libraries Government Documents Department
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Scintillation Spectrometry : Gamma-Ray Spectrum Catalogue

Description: Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.
Date: July 1, 1957
Creator: Heath, R. L.
Partner: UNT Libraries Government Documents Department
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Summary of the Spert-I, -II, and -III reactor facilities

Description: Report containing "[a] brief description and design data summary of each of the SPERT Reactor Facilities is presented. Engineering, operating, and physics data are tabulated for use as basic references" (p. 3)
Date: November 1, 1957
Creator: Montgomery, C. R.; Norberg, J. A. & Wilson, T. R.
Partner: UNT Libraries Government Documents Department
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Engineering Test Reactor Critical Facility Hazards Summary Report, Supplement I

Description: Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).
Date: January 24, 1958
Creator: deBoisblanc, D. R.; Burdick, Earl E. & DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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Source Strength Information for Shielding and Stack Effluent Calculations: a Standard Practices Guide

Description: Report presenting the curves and methods used "for determining gross fission product gamma energy in Mev/sec-watt, gross fission product beta decay in curies/sec-watt, delayed uranium fission neutrons in neutrons/sec-watt and N16 and N17 decay in photons/sec-cc of water" (p. 1).
Date: October 3, 1958
Creator: Jones, L. H.
Partner: UNT Libraries Government Documents Department
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Maintenance of ETR Coolant

Description: Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).
Date: August 15, 1958
Creator: Haas, F. C.
Partner: UNT Libraries Government Documents Department
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Standard Practices Guide for Writing Experimental Operating Manuals

Description: This is a sample operating manual designed to aid experimenters in writing operating manuals for MTR and ETR experiments. It contains what is felt to be the necessary information for operating a particular experiment. One of the main functions of an operating manual is to provide quick reference to material needed in an emergency. It is believed this type of manual provides the required information without an excessive amount of bulky, surplus material.
Date: December 15, 1958
Creator: Ford, J. D.
Partner: UNT Libraries Government Documents Department
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Experimental Organic Cooled Reactor : Conceptual Design

Description: Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date: December 1, 1959
Creator: Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
Partner: UNT Libraries Government Documents Department
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The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Partner: UNT Libraries Government Documents Department
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Generalized Heat Conduction Code for the IBM-704 Computer

Description: Report regarding a code that solves "steady-state and/or transient heat conduction problems in three-dimensional geometry" (p. 1).
Date: 1959
Creator: Fowler, T. B. & Volk, E. R.
Partner: UNT Libraries Government Documents Department
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